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Abstract
The correlation between microstructure and mechanical property of ion irradiated 12Cr-6Al ODS ferritic steel was studied. Ion irradiation experiments were performed using 10.5 MeV Fe ions up to the nominal displacement damage of 20 dpa with the damage rate of 1 × 10−4 dpa/s, while the irradiation temperature was 300 °C. Oxide nanoparticles showed stable size distribution and mean size under ion irradiation up to 20 dpa. The irradiation microstructure examined by TEM revealed that the mean size and number densities of irradiation-induced defect clusters increased with the displacement damage. The correlation between irradiation microstructure and radiation hardening was theoretically calculated using the dispersed barrier hardening model. The results showed a good agreement with the experimentally measured hardness data up to irradiation at 5 dpa, while a slight discrepancy was found between theoretical and experimental hardness values under irradiation at 20 dpa. Radiation hardening in 12Cr-6Al ODS ferritic steel was mainly caused by irradiation-induced defect clusters below the irradiation dose of 5 dpa. As the irradiation dose increased toward 20 dpa, an additional influence of the radiation appeared, which was assumed to be induced by α’ phase transformation.
Highlights
With the growing interest in oxide dispersion strengthened (ODS)ferritic/martensitic and ferritic steels utilized to various nuclear applications, extensive research on those steels have revealed their strength at high temperature and microstructural stability under irradiation conditions
The optimization of solute content in ODS steels has been made for the purpose of improving mechanical, chemical and irradiation resistant properties, enabling the withstanding at high operating temperature of fusion reactors
The present paper reports the fundamental irradiation effect on the mechanical property and related microstructural evolution in the 12Cr-6Al ODS ferritic steel
Summary
Ferritic/martensitic and ferritic steels utilized to various nuclear applications, extensive research on those steels have revealed their strength at high temperature and microstructural stability under irradiation conditions. The optimization of solute content in ODS steels has been made for the purpose of improving mechanical, chemical and irradiation resistant properties, enabling the withstanding at high operating temperature of fusion reactors. ODS ferritic steels with a high chromium content often experiences the formation of Cr rich α’ phase by thermal aging at above 400 °C [1] or by irradiation at a low temperature [2]. The corrosion resistance is reduced by the decrease in chromium content, it could be compensated by addition of aluminum in the matrix of ODS ferritic steels. The advantageous effect of aluminum on the corrosion property of ODS ferritic steels was reported by Kimura et al, and the mechanisms was explained by the formation of stable Al2O3 oxide layer together with the (Cr, Fe)2O3 layer [3,4]. Fig. 1. 10.5 MeV Fe ion irradiation up to the irradiation dose of 1 dpa at the depth of 1 μm
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